ML20214A290

Monthly Operating Repts for Oct 1986

ML20214A290
Person / Time
Site:	Oconee
Issue date:	10/31/1986
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8611190374
Download: ML20214A290 (19)

Text

F

• y OPERATING DATA REPORT DOCKET NO.

50-269 DATE Il-14-86 CONIPLETED BY J.A-Reavis TE!.EPHONE 704-373-7567 OPERATING STATUS OC "** 1 N

5

1. Unit Name:

Year-to-date and cumulative

2. Reporting Period: October 1. 1986-October 31. 1986 2568 capacity factors are calcu-

3. Licensed Thermal Power (31Wt):

934 lated using a weighted

4. Nameplate Rating (Gross SIWE):

average for maximum 886

5. Design Electrical Rating (Net alWe):

dependable capacity.

' 6. Sfaximum Dependable Capacity (Gross alWe):

899 860

7. Staximum Dependable Capacity (Net SIWE):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level To which Restricted,If Any (Net.\\lwe):

Nne

10. Reasons For Restrictions,if Any:

This Stonth Yr. to-Date Cumulative

11. Hours In Reporting Period 745.0 7 296.0 116 545.0

12. Number Of Hours Reactor Was Critical 360.8 4 484.6 84 930.9

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 355.1 4 408.6 81 538.2

15. Unit Resene Shutdown Hours 884 424 10 961 873 197 262 073

16. Gross Thermal Energy Generated (51WH)

17. Gross Electrical Energy Generated (SiWH) 298 330 3 770 490 68 517 330

18. Net Electrical Energy Generated (SIWH) 280 086 3 566 950 64 965 199

19. Unit Service Factor 47.7 60.4 70.0

20. Unit Availability Factor 47.7 60.4 70.0

21. Unit Capacity Factor (Using SIDC Net) 43.7 56.9 64.7

22. Unit Capacity Factor (Using DER Net) 42.4 55.2 62.9

23. Unit Forced Outage Rate 52.3 17.6 15.1

24. Shutdowns Scheduled Over Next 6 31onths (Type. Date,and Duration of Each):

i None f.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status t Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY CO\\1NIERCIAL OPER ATION 1

(9/77 )

8611190374 861031 PDR ADOCK 05000269 h

(h

AGERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-269 UNIT Oconee 1 6

flATE November 14, 1986 COMPLETED J. A. Reavis 8

TELEPHONE 704-373-7567 MONTH October, 1986 DAY AYERAGE DAILY POWER LEYEL DAY AVERACE DAILY POWER LEYEL (MWE-Net 1 (ME-Neti 1

833 17

,0 2

484 18 0

3 0

19

~489 4

a 20 814 5

0 21 821 6

0 22 828 7

0 23 835 8

0 24 8 835 9

0 25 841 10 0

26 841 11 0

27 838 12 0

28 827 13 0

29 840 14 0

30 840 15 0

31 831*

16 0

Y j.

I i

t

--g

.,e

- - - -, -.. - +

UNIT SHUTDOWNS AND POWER REDUCTI0'JS DOCKET N0.

50-269 UNIT NAME oconee 1 DATE 11/14/86 Page 1 of 2 REPORT MONTH october 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s

O

'e o,$

License y

Cause & Corrective c

.S 7 "c

c a

o 3;;3 v

Event h

g No.

Date gy Action to o

c 5E E

US$

EE 8"

ud Prevent Recurrence H

ov a:

xmo Report #

ma 53-p 86-10-02 F

A ZZ ZZZZZZ Cold Leg Differential High 54-p 86-10-02 S

F ZZ ZZZZZZ System Demand per Dispatcher 10 86-10-02 F

389.92 A

1 WA PUMPXX Low Press. Serv. Water Pumps Inoperable, Loss of Condenser Cooling Water (Gravity Flow Test) 55-p 86-10-19 F

A IF INSTRU Integrated Control System Problems 56-p 86-10-19 F

A XX PIPEXX "LPE-10" Extraction Line Problem 57-p 86-10-19 F

B ID INSTRU Nuclear Instrumentation Calibration 58-p 86-10-19 F

A CH HTEXCH High Steam Generator Levelt, 59-p 86-10-27 S

B HC PUMPXX Drain Condensate Air Ejector; Lines 60-p 86-10-27 F

A HC XXXXXX Decreased Vacuum 61-p 86-10-28 F

A CH HTEXCH High Steam Generator Levels 62-p 86-10-28 F

A CH xxxxxx Feedwater Swing 63-p 86-10-28 F

A HH PUMPXX Loss of "lD2" Heater Drain Pump 1

1 2

3 4

Reason:

Method:

Exhibit G - Instructions SS led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training 4 License Examination F-Administrative S

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(9/77)

)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0.

50-269 UNIT NAME Oconee 1

~

DATE 11/14/86 Page 2 of 2 REPORT MONTH October 1986 COMPLETED BY J. A. Reavis TELEPHONE 704-373-7567 "s.

O tj License y

Cause & Corrective cS7 "c

v"E g

No.

Date

~.

%h g

jg Event je, g

Action to Report #

h bb Prevent Recurrence 64-p 86-10-28 F

A CH HTEXCH High Steam Generator Levels 65-p 86-10-31 S

B HC PUMPXX Drain Condensate Air Ejectorr Lines 66-p 86-10-31 F

A HC HTEXCH High Steam Generators Levels

)

i 1

2 3

4 Reason:

Method:

Exhibit G - Instructions SS led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training 6 License Examination F-Adninistrative 5

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(9/77)

DOCKET NO: 50-269 UNIT: Oconee 1 DATE: 11/14/86 NARRATIVE

SUMMARY

Month: October 1986 Oconee Unit 1 began the month at 100% power. On 10/02 the unit averted a trip when Feedwater to the Steam Generators re-ratioed. The unit returned to 98% but was forced to shut down on 10/02 because of a safety question concerning the Low Pressure Service Water System and the Siphon effect of the Condenser.

The unit returned to service on 10/19 and increased power to 99%. The unit is limited to that power level due to high Steam Generator levels.

It remained at 99% for the rest of the month.

1 I

a 1

i t

a i

I l

[

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Oconee, Unit 1 2.

Scheduled next refueling shutdown:

August, 1987 3.

Scheduled restart following refueling: October, 1987 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

177 1

(b) in the spent fuel pool:

989*

8.

Present licensed fuel pool capacity:

1312 j

Size of requested or planned increase:

l l

9.

Projected date of last refueling which can be accommodated by present licensed capacity: August, 1991 l

l l

DUKE POWER COMPANY DATE: November 14, 1986 Name of

Contact:

J. A. Reavis Phone:

704-373-7567

• Represents the combined total for Units 1 and 2.

l l

m.

OPERATING DATA REPORT DOCKET NO.

50-270 DATE 11-14-86 COMPLETED BY J.A. Reavis TELEPHONE 704-373-7567 GPERATING STATUS Oconee 2

. Notes

1. Unit Name:

2. Reporting Period: October 1. 1986-october 31. 1986 Year-to-date and cumulative

3. Licensed Thermal Power (MWt):

256a capacity factors are calcu-

4. Nameplate Rating (Gross MWe):

934 lated using a weighted

5. Design Electrical Rating (Net MWe):

886 average for maximum 899 dependable capacity.

6. Maximum Dependable Capacity (Gross MWe):

860

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None None

9. Power Level To Which Restricted,if Any (Net MWel:

10. Reasons For Restrictions. If Any:

This Month Yr to.Date Cumulative i1. Hours in Reporting Period 745~.0 7 296.0 106 465.0

12. Number Of Hours Reactor Was Critical 355.3 5 789.6 78 627.2

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 299.6 5 707.6 77 309.1

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 666 240 14 442 223 184 846 126

17. Gross Electrical Energy Generated (MWH)

'223 540 4 881 970 62 016 111

18. Net Electrical Energy Generated (MWH) 206 214 4 658 112 59 825 673

19. Unit Service Factor 40.2 78.2 72.6

20. Unit Availability Factor 40.2 78.2 72.6

21. Unit Capacity Factor (Using MDC Net) 32.2 74.2 65.2

22. Unit Capacity Factor (Using DER Net) 31.2 72.1 63.4

23. Unit Forced Outage Rate 3.2 0.9 13.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

Mnno

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status t Prior to Commercial Operation):

Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY i

COMMERCIAL OPER ATION i

(o/77 )

I

r AYERACE DAILY UNIT POWER LEYEL DOCKET NO 50-270 UNIT Oconee 2 04TE November 14, 1986 COMPLETED J. A. Reavis TELEPHONE 704-373-7567 NONTH October, 1986 DAY AYERACE DAILY POWER LEVEL DAY AYERACE DAILY POWER LEVEL INWE-Net!

(MWE-Net) 1 0

17 0

2 0

18 0

3 0

19 161 4

0 20 531 5

0 21 619 6

0 22 768 7

0 23 454 8

0 24 653 9

0 25 807 10 0

26 806 11 0

27 806 12 0

28 801 13 0

29 900 14 0

30 000 15 0

31 798 16 0

i

,p s

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0. 50-270 UNIT NAME oconee 2 DATE 11/14/86

~

REPORT MDNTH october 1986 COMPLETED BY J. A. Reavis Page 1 of 2 TELEPHONE 704-373-7567 "s_

B

% o, g

. License y

Cause & Corrective cS7 "c

e"E No.

Date

%h 3-pg, Event

,5e, h

Action to

~ a 5

o ~E E

%S$

EE 83 a:

c m o Report #

mo uo Prevent Recurrence 5

86-10-01 S

432.65 C

1 RC FUELXX End of Cycle 8 Refueling Outage 53-p 86-10-19 F

A HA XXXXXX Underexcitation Reactive Ampere Limit Work 6

86-10-19 S

2.88 B

4 HA CENERA Turbine Overspeed Trip Test (Reactor Remained Critical) 54-p 86-10-19 S

B IB INSTRU Nuclear Instrumentation Calibration 55-p 86-10-19 S

B RC xxxxxx Power Escalation Testing 56-p 86-10-20 S

B RC XXXXXX Power Escalation Testing 57-p 86-10-20 S

B RC XXXXXX Fower Escalation Testing 58-p 86-10-21 S

B RC XXXXXX Power Escalation Testing 59-p 86-10-22 F

B ZZ ZZZZZZ Adjust Cold Leg Temperature Differentia:.

60-p 86-10-22 F

A CC VALVEX Control Valve "3" Failed Open 61-p 86-10-23 F

A CH HTEXCH High Steam Generator Level 7

86-10-23 F

9.85 A

3 CH HTEXCH High Steam Generator Level 4

1 2

3 4

Reason:

Method:

Exhibit G - Instructions SS led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Mmual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training 4 License Examination F-Adninistrative 5

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(9/77)

l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0.

50-270 UNIT NAME oconee 2 DATE 11/14/86 REPORT MONTH October 1986 COMPLETED BY J. A. Reavis Page 2 of 2 TELEPHONE 704-373-7567

~

io o en$

License y

Cause & Corrective e32 "a

v5E Ns.

Date

~.

gh pg Event h

h Action to o-ES E

%Eb E3 53 H

o-o:

Emo Report #

ma vu Prevent Recurrence 62-P 86-10-24 F

A CH XXXXXX Secondary Swing 63-P 86-10-24 F

A CH HTEXCH High Steam Generator Level 64-P 86-10-31 F

B ZZ ZZZZZZ Stroking "2FDW-36" and "2FDW-45" Feedwater Control Valves 65-p 86-10-31 F

A CH HTEXCH High Steam Generator Level 1

2 3

4 Reason:

Method:

Exhibit G - Instructions SS led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NLREG-0161)

E-Operator Training 6 License Examination F-Adninistrative 5

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(9/77)

~

DOCKET NO: 50-270 UNIT: Oconee 2 DATE: 11/14/86 NARRATIVE SUbefARY Month: October 1986 Oconee Unit 2 began the month in its End of Cycle 8 refueling outage.

It

-returned on 10/19 and performed a Turbine Trip test.

The unit went on line later that day and increased power over the next 3 days to 92% with power holds at various levels for Power Escalation testing. On 10/24, the unit tripped during a feedwater swing caused by an instrument failure. The unit, returned to service on 10/25, escalated power to 95% and operated at that level for the remainder of the month. The unit is currently limited to 95%

power because of high Steam Generator levels.

l i

l l

f.

l i

i c

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Oconee, Unit 2 2.

Scheduled next refueling shutdown: December, 1987 3.

Scheduled restart following refueling: March, 1988 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

177 (b) in the spent fuel pool:

989*

8.

Present licensed fuel pool capacity:

1312 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity: August, 1991 i

DUKE POWER COMPANY DATE: November 14, 1986 Name of

Contact:

J. A. Reavis Phone:

704-373-7567

• Represents the combined total for Units I and 2.

l i

OPERATLNG DATA REPORT DOCKET NO.

50-287 DATE 11-14-86 CO31PLETED BY JA. Reavis TELEPHONE 704-373-7567 OPERATING STATUS

1. Unit Name:

oc nee 3 Notes

2. Reporting Period: nernhar 1.

1OR6_ncenhor 11. toga Year-to-date a.nd cumulative

3. Licensed Thermal Power (SIWr):

2568 capacity factors are calcu-

4. Nameplate Rating (Gross SIWE):

934 lated using a weighted

5. Design Electrical Rating (Net SIWE):

886 average for maximum

6..\\laximum Dependable Capacity (Gross SIWE):

ggg dependable capacity.

7. Maximum Dependable Capacity (Net SIWE):

860

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None

. 9. Power Level To which Restricted.If Any(Net 31We):

10. Reasons For Restrictions. lf Any:

i 3

This 3!onth Yr..to.Date Cumulative

11. Hours in Reporting Period 745.0 7 296.0 104 112.0

12. Number Of Hours Reactor Was Critical 176.8 6 712.4 76 083.8

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 155.8 6 661.1 74 793.6

15. Unit Resene Shutdown Hours 16.. Gross Thermal Energy Generated (SIWH) 313 080 16 677 008 183 345 454

. 17. Gross Electrical Energy Generated (5!WH) 106 370 5 648 390 63 176 444

18. Net Electrical Energy Generated (31WH) 93 603 5 393 756 60 173 113 l

19. Unit Service Factor 20.9 91.3 71.8 20 Unit Availability Factor 20.9 91.3 71.8 J

21. Unit Capacity Factor (Using SIDC Net) 14.6 86.0 67.1 l

22. Unit Capacity Factor (Using DER Net) 14.2 83.4 65.2

23. Unit Forced Outage Rate 79.1 8.7 14.1

24. Shutdowns Scheduled Over Nest 6 Stonths (Type.Date,and Duration of Each):

wnn

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIA L ELECTRICITY COllstERCIAL OPER ATION I

i l

1o/77:

1

F_

AYERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-287 UNIT Oconee 3 DATE Noveober 14, 1996 COMPLETE 0 J. A. Reavis TELEPHONE 704-373-7567 MONTH October, 1986 DAY AY DACE DAILY POWER LEYEL DAY AYERACE DAILY POWER LEVEL tMWE Net 1 IMWE-Neti 1

805 17 0

2 421 18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 512 8

0 24 654 9

0 25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 576 14 0

30 616 I

15 0

31 608 16 0

l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET N0. 50-287 UNIT NAME oconee 3 DATE 11/14/86 REPORT MONTH october 1986 COMPLETED BY J. A. Raavis TELEPHONE 704-373-7567 "s_

O

'$ en$

License y

Cause & Corrective c27 "c

u"a No.

Date

~.

%h g

3gc Event h

h Action to 5E E

%55 RE 8"

H o-n:

xmo Report #

mu ud Prevent Recurrence 4

86-10-02 F

491.50 A

1 WA PUMPXX Loss of Suction to Low Pressure Service Water Pumps During Gravity Flow Test 30-p 86-10-23 F

B IB INSTRU Nuclear Instrumentation Calibration 31-p 86-10-24 F

A CB PUMPXX "3Bl" Reactor Coolant Pump 011 Leak 5

86-10-25 F

97.70 A

1 CB PUMPXX "3Bl" Reactor Coolant 1-ump Oil Leak 32-p 86-10-29 F

H RB XXXXXX Deboration 33-p 86-10-29 F

A HH PUMPXX Low Condensate Booster Pump Pressure 34-p 86-10-29 F

A HH VALVEX "3C-61" Condensate Flow Around Coolers Control Valve Problems 35-p 86-10-29 F

A HH PUMPXX "3E2" Heater Drain Pump Out of Service 36-p 86-10-30 F

A CB PUMPXX High Vibrations and Noise on "3Bl" Reactor Coolant Pump 37-p 86-10-30 F

A CH HTEXCH High Steam Generator Level i

1 2

3 4

Reason:

Method:

Exhibit G - Instructions S Sc e led A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER)

D-Regulatory Restriction 4-Other (Explain)

File (NUREG-0161)

E-Operator Training 4 License Examination F-Adninistrative S

G-Operational Error (Explain)

Exhibit I - Same Source H-Other (Explain)

(9/77)

DOCKET NO: 50-287 UNIT: Oconee 3 DATE: 11/14/86 NARRATIVE

SUMMARY

Month: October 1986 Oconee Unit 3 began the month at 100%, but was forced off line on 10/02 by the same safety questions that affected Unit 1.

The unit returned to service on 10/23 and increased power to 100%. On 10/25 the unit was shut down to add oil to a Reactor Coolant pump and make repairs to the pump's lower oil pot.

The unit returned to service on 10/29 and began its increase to 100%. The unit detected noise and high vibration on the pump while at 97% and was forced to reduce power to 67% and remove the pump from service on 10/30. The unit is able to operate with 3 pumps but only at 75% power. The unit is operating at 71% and is limited by feed flow.

l l

t i

l l

l L

r 2

MONTHLY REFUELING INFORMATION REQUEST 1.

Facility name: Oconee, Unit 3 2.

Scheduled next refueling shutdown:

February, 1987 3.

Scheduled restart following refueling: April, 1987 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

177 (b) in the spent fuel pool: 469 8.

Present licensed fuel pool capacity: 875 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity: August, 1991 DUKE POWER COMPANY DATE: November 14, 1986 Name of

Contact:

J. A. Reavis Phone:

704-373-7567

6 OCONEE NUCLEAR STATION MONTHLY OPERATING STATUS REPORT 1.

Personnel Exposure For the month of September, no individuals exceeded 10 percent of their allowable annual radiation dose limit.

2.

The total station liquid release for September has been compared with the Technical Specifications maximum annual dose comitment and was less than 10 percent of this limit.

The total station gaseous release for September has been compared with the Technical Specifications maximum annual dose comitment and was less than 10 percent of this limit.

I T

l l

DUKE POWER GOMPAhT P.O. HOx 33180 CHARLOTrE, N.C. 28242 HALB. TUCKER TELEPHONE VM.EPerstDENT (704) 373-4531 winsam emoot:criom November 14, 1986 Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Re: Oconee Nuclear Station Docket No. 50-269, -270, -287

Dear Sir:

Please find attached information concerning the performance and operating status of the Oconee Nuclear Station for the month of October, 1986.

Very truly yours, h/A Hal B. Tucker JAR /03/slb Attachment 1

xc:

Dr. J. Nelson Grace, Regional Administrator American Nuclear Insurers U. S. Nuclear Regulatory Commission c/c Dottie Sherman, ANI Library Region II The Exchange, Suite 245 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue Atlanta, Georgia 30323 Farmington, CT 06032 Mr. Phil Ross INPO Records Center U. S. Nuclear Regulatory Consnission Suite 1500 MNBB-5715 1100 Circle 75 Parkway Washington, D. C.

20555 Atlanta, Georgia 30323 Ms. Helen Pastis, Project Manager Ms. Judy Dovers Office of Nuclear Reactor Regulation Nuclear Assurance Corporation U. S. Nuclear Regulatory Commission 5720 Peachtree Parkway Washington, D. C.

20555 Norcross, Georgia 30092 Mr. J. C. Bryant NRC Resident Inspector

((

Oconee Nuclear Station v i 1